Published 1995
| Version v1
Journal article
A RELAP5/MOD3 simulation of loss of residual heat removal system after reactor
Description
A computational investigation of the experiment concerning the loss of the residual heat removal system (RHRS) during reduced inventory operation was simulated using the RELAP5/ MOD3 thermal-hydraulic code. The experiment was conducted at the UMCP 2 x 4 integral test loop (University of Maryland) and consisted of two parts: loss of RHRS and loss of feedwater system. The objective of the work presented in this paper is to assess the capability of the RELAP5 code to capture the phenomena observed in the experiment during the boiler-condenser mode (BCM) and the loss of feedwater (LOFW) system transient
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 72
- Journal Page Range
- p. 404-406.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- Annual meeting of the American Nuclear Society (ANS).
- Dates
- 25-29 Jun 1995.
- Place
- Philadelphia, PA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27036645
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FEEDWATER; HYDRAULICS; PWR TYPE REACTORS; R CODES; REACTOR COOLING SYSTEMS; TEST FACILITIES
- Descriptors DEC
- COMPUTER CODES; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-950601--.